Method and system for detecting an explosive

ABSTRACT

A method and system for detecting at least one explosive in a vehicle using a neutron generator and a plurality of NaI detectors. Spectra read from the detectors is calibrated by performing Gaussian peak fitting to define peak regions, locating a Na peak and an annihilation peak doublet, assigning a predetermined energy level to one peak in the doublet, and predicting a hydrogen peak location based on a location of at least one peak of the doublet. The spectra are gain shifted to a common calibration, summed for respective groups of NaI detectors, and nitrogen detection analysis performed on the summed spectra for each group.

RELATED APPLICATIONS

This application is a continuation of U.S. patent application Ser. No.12/358,883, filed Jan. 23, 2009, entitled “METHOD AND SYSTEM FORCALIBRATING ACQUIRED SPECTRA FOR USE IN SPECTRAL ANALYSIS,” now U.S.Pat. No. 7,795,595, issued Sep. 14, 2010, which application is acontinuation of U.S. patent application Ser. No. 11/877,192, filed Oct.23, 2007, entitled “METHOD AND SYSTEM FOR DETECTING EXPLOSIVES,” nowU.S. Pat. No. 7,501,637, issued Mar. 10, 2009, which is a divisional ofU.S. patent application Ser. No. 11/100,800 filed Apr. 6, 2005, entitled“EXPLOSIVES DETECTION SYSTEM AND METHOD,” now U.S. Pat. No. 7,307,256,issued Dec. 11, 2007, the entire disclosure of each of which isincorporated herein by this reference.

GOVERNMENT RIGHTS

This invention was made with government support under Contract No.DE-AC07-991D13727 and Contract No. DE-AC07-051D14517 awarded by theUnited States Department of Energy. The government has certain rights inthe invention.

TECHNICAL FIELD

The present invention relates to systems and methods for protectingagainst terrorism. More particularly, the invention relates to systemsand methods for detecting explosives.

BACKGROUND OF THE INVENTION

There is a need for an explosive detection system to detect bombs invehicles of various sizes, from cars to large trucks. When vehiclesenter an area, such as a military base, they are inspected visually.They are perhaps inspected by a canine unit, if one is available, andmany times they are not available. The inspection time must be shortenough so as not to hamper traffic flow.

Currently, vehicles entering facilities such as military bases andembassies are checked for explosives by physical search, x-ray, vapordetection, or canine units.

Attention is directed to the following references: [1] P. C. Womble, G.Vourvopoulos, J. Paschal, I. Novikov, G. Chen, “Nuclear Instruments andMethods in Physics Research,” Sect. A Vol. 505, p.p. 470-473 (2003); [2]T. Gozani, M. Elsalim, D. Strellis, D. Brown, “Nuclear Instruments andMethods in Physics Research,” Sect. A Vol. 505 p.p. 486-489 (2003); and[3] G. Vourvopoulos, “Chemistry and Industry,” p.p. 297-300 (Apr. 18,1994).

BRIEF DESCRIPTION OF THE DRAWINGS

Preferred embodiments of the invention are described below withreference to the following accompanying drawings.

FIG. 1 is a front view of a system embodying various aspects of theinvention.

FIG. 2 is a top diagrammatical view of the system of FIG. 1.

FIG. 3 is a screen shot of a graphical user interface of the system ofFIG. 1.

FIG. 4 is a screen shot of the graphical user interface of FIG. 3 duringthe process of neutron generator start-up.

FIG. 5 is a screen shot of the graphical user interface of FIG. 3 duringthe process of interrogation.

FIG. 6 is a screen shot of the graphical user interface of FIG. 3 aftera determination that no explosives are present.

FIG. 7 is a screen shot of the graphical user interface of FIG. 3 aftera determination that explosives are present.

FIG. 8 is a diagrammatical map illustrating the general locations ofdetectors.

FIG. 9 is a high level flowchart illustrating logic implemented by thecontrol system.

FIG. 10 is a flowchart illustrating calibration of FIG. 9 in greaterdetail.

FIG. 11 is graph showing an example of a typical NaI spectrum, whichincludes a Na/Annihilation doublet, a Hydrogen peak, and a Na peak.

FIG. 12 is a graph illustrating Gaussian peak fitting to a doubletdefined by a sodium peak and an annihilation peak.

FIG. 13 is a graph illustrating Gaussian peak fitting to a hydrogenpeak.

FIG. 14 is a graph illustrating Gaussian peak fitting to a sodium 6867peak.

FIG. 15 is a cut-away perspective view of one of the racks.

FIG. 16 illustrates spacing between components in a rack, in oneparticular embodiment.

FIGS. 17A and 17B comprise a screen view of an example of anadministrator level screen using operating parameters of detectors thatcan be set.

FIG. 18 is a screen view of an example of an administrator level screenusing operating parameters of generators that can be set.

FIG. 19 is a screen view of an example of an administrator level screenusing operating parameters such as threat level settings and otheritems, as shown, that can be set.

DESCRIPTION OF THE INVENTION

This disclosure of the invention is submitted in furtherance of theconstitutional purposes of the U.S. Patent Laws “to promote the progressof science and useful arts” (Article 1, Section 8).

The invention provides an explosives detection system and method thatdetects an explosive inside a vehicle by use of multiple detectors. Acombination of detectors is used to detect an explosive in a shortamount of time.

FIG. 1 shows a system 10 for detecting explosives, and embodying variousaspects of the invention. The system 10 has many anti-terrorismapplications including, for example, detecting vehicles carryingexplosives, e.g., into restricted areas or military bases. In theillustrated embodiment, the system 10 includes two racks, 12 and 14,capable of being moved to each side of a subject vehicle 16. Each rack12 and 14 includes a neutron generator 18 and an array of detectors 20,such as NaI detectors (FIG. 2). The two neutron generators 18 are pulsedand synchronized. A controller, which can be defined, for example, by alaptop computer, controls the racks 12 and 14. The control software iseasily operable by minimally trained staff. The system 10 was developedto detect explosives in a vehicle within a short time. Moreparticularly, in the illustrated embodiment, the system 10 can detectexplosives in a medium size truck within a five-minute measurement time.

In the illustrated embodiment as shown in FIG. 2, the system 10 uses twopulsed D-T neutron generators 18 to interrogate the vehicle 16. In theillustrated embodiment, the neutron generators 18 are Genie 16-C neutrongenerators available from Sodern, 20 Descartes Avenue, Limeil-Brévannes,France. Other neutron generators could be employed. While otherembodiments are possible, in the illustrated embodiment, 14 MeV neutronsare produced. High-energy neutrons penetrate the subject vehicle 16where they interact with any explosive in or on the vehicle. Some ofthese neutrons are thermalized within the explosive and are captured bythe nitrogen atoms. More particularly, some of the neutronsinelastically scatter off various elements until they eventuallythermalize and are captured. These interactions release signature gammarays from the explosive, which are measured by the large array of NaIdetectors 20. Explosives are chemically distinct from innocuousmaterials. When a neutron is captured by a nitrogen atom, a 10.8 MeVgamma ray is released. The gamma ray spectra, acquired using thedetectors 20, are analyzed to identify the major elemental components ofthe explosives. While other numbers could be employed, in theillustrated embodiment, there are thirty-two NaI 5×5 detectors.

After the detection period is complete, all the spectra from thedetectors are automatically calibrated and gain matched to the samelinear equation. After this is done, the spectra can be added together.If the detection time is long enough, the detectors do not have to beadded and can have enough statistics to indicate detection ofexplosive(s). The adding of detectors allows for a shorter detectiontime. The detectors are added together in groups ranging from four toeight detectors. The group members are determined by the closestdetectors to any particular point in the suspect vehicle. For example,to detect an explosive located in the far back of the truck, thedetectors on both ends of the racks are the closest and will be the mostlikely to detect the explosives. By having a wide variety of groups, thesensitivity of detection is increased. Also, by not adding all thedetectors together, which would include detectors that are out of rangeof target, the signal to background ratio is kept high. In someembodiments, any one detector does not have enough statistics toconclusively determine whether an explosive is present or not. By addingseveral detectors together, there will be enough statistics to determinewhether an explosive is present or not. The grouping of detectors isselected so as to group together detectors that are a similar distancefrom a certain spot in the vehicle.

An alarm condition is provided when the system detects certain elementsin certain minimum quantities.

In the illustrated embodiment, a control system 22, coupled to theneutron generators 18 and detectors 20, is used to control operation ofthe neutron generators 18 and process and analyze data received from thedetectors 20, and give a result. The control system 22, in variousembodiments, may also monitor the health of the system, monitor theinterrogation progress, and give a result in a clear, simple, go orno-go format.

In operation, the inspection of a subject vehicle 16 (FIG. 1) beginswith the vehicle 16 driving into position between the two identicalracks 12 and 14. After the driver exits the vehicle 16 and the radiationexclusion zone, the racks 12 and 14 are moved close to the vehicle. Thisis referred to as “pinching” the vehicle. In the illustrated embodiment,there is, for example, a 2-mrem-per-hour radiation exclusion zone whichis approximately 90 feet long by 60 feet wide. The operator of thesystem 10 is located outside this zone. In the illustrated embodiment,the operator is up to 4000 feet away. In the illustrated embodiment,each rack 12, 14 includes an array of 5-inch diameter by 5-inch deepsodium iodide (5×5 NaI) detectors, defining the detectors 20, andshielding. After the vehicle 16 is pinched, the neutron generators 18are turned on and warmed up. After warm-up, the neutron interrogationbegins. In the illustrated embodiment, the warm-up time is approximately85 seconds.

In the illustrated embodiment, the control system 22 includesphotomultiplier tube bases 24 and spectrum analyzers for gamma rayspectroscopy. The control system 22 further includes a processor coupledto the photomultiplier tube bases 24. More particularly, in theillustrated embodiment, the photomultiplier tube bases 24 are defined bydigiBASEs® available from Ortec, 801 South Illinois Avenue, Oak Ridge,Tenn. 37830 (see http://www.ortec-online.com/pdf/digibase.pdf). EachdigiBASE® also includes an integrated bias supply, preamplifier anddigital multi-channel analyzer. In the illustrated embodiment, theprocessor is defined by a computer 26, such as a portable or laptopcomputer. More particularly, in the illustrated embodiment, all thedigiBASEs® are connected to the control laptop computer 26 by USB cablesthrough USB hubs, which provide power to the photomultiplier tube bases24. In the illustrated embodiment, the only other connection on thedigiBASE® is a gating input. Data are collected and stored by thedigiBASEs® during the interrogation. Periodically during theinterrogation the stored data are read from all the digiBASEs® at a USBrate. Because the data are read in spectrum form from the digiBASEs®,the speed of the USB is not crucial. Alternative connection types andalternatives to digiBASEs® could also be employed.

When the interrogation is complete, a spectrum is read from eachdetector 20. The spectra are then calibrated. In the illustratedembodiment, the calibration is automatic, and is accomplished, forexample, by using always-present gamma rays including Hydrogen at 2.2MeV. Spectra with calibration coefficients outside preset ranges arerejected and not analyzed. After the initial individual calibrationoccurs, spectra are shifted to one common calibration, which allows thespectra to be added together. Calibration is described in greater detailbelow. The spectra are then analyzed for signature gamma rays. Dependingon the results of the analysis, the operator is alerted with an “AllClear” message indicating no explosives detected or a “Suspect Cargo”message indicating that explosives were detected. In the illustratedembodiment, a simple, very clear go or no-go output is displayed thatcan be easily understood by an operator without the operator needing toreach his or her own conclusion or needing to analyze results. At anadministrator-defined interval during the interrogation, preliminaryresults can be given. The entire interrogation and analysis time,including the neutron generator warm-up time, is less than 300 seconds(five minutes), in the illustrated embodiment.

In some embodiments, the system 10 includes a feature that allows anoperator to change the sensitivity of the system 10 in response tochanges in facility alert status. In some embodiments, the desiredsensitivity is selected by choosing one of multiple threat levels (e.g.,Alpha, Bravo, Charlie, or Delta). Each level corresponds to a differentbalance of count time, false positive and false negative rates.

In the illustrated embodiment, one of the design considerations for thesystem 10 was to maximize the signal-to-noise ratio. To maximize thesignal, highly efficient 5×5 NaI detectors with factory quotedresolutions ranging from 6.5% to 7.4% using a 137Cs source were chosen.A disadvantage of the NaI detectors is that their gain changes withneutron activation. This is counteracted by the gain stabilizer builtinto the digiBASE® and by the calibration steps described below ingreater detail. Gain changes of the NaI detectors due to temperature aremuch less significant than due to the neutron activation, and are alsominimized because material surrounding the detectors reduces thetemperature fluctuations.

In the illustrated embodiment, the detectors 20 are distributed over thelength of a typical mid-size delivery truck. In the illustratedembodiment, on each side of the subject vehicle 16, there are sixteendetectors plus a neutron generator 18 distributed over about 16.5 feetwith the detectors 20 in two rows spaced apart. This arrangement meansthere will be a detector close to the explosives no matter where theyare located in the subject vehicle 16. Other spacings are possible. Inthe illustrated embodiment, the arrangement of the detectors 20 wasselected to be able to cover the entire cargo area of a mid-sized truck(up to 20 ft). But there is a distance limit from the neutron generators18 where the neutron flux drops off to a level that doesn't allow enoughproduction of nitrogen gamma rays to be detected. The detectors 20should also be close enough to each other so that they can be summedtogether so that a statistically significant amount of nitrogen can bedetected.

Signal strength can be further improved by raising the flux of neutronsinterrogating the vehicle. Adding more neutron generators or usinghigher flux neutron generators can achieve this. Both of these optionsare costly. The addition of a neutron generator would raise the cost ofa system significantly and running a neutron generator at a higherneutron flux output would reduce the lifetime of the neutron generatortube, increasing maintenance costs.

Another way of increasing the signal-to-noise ratio is to reduce thebackground seen by the detectors. In the illustrated embodiment, ashielding configuration is provided that blocks the detectors fromneutrons from the generators as well as unwanted gamma rays producedfrom surrounding materials. This shielding reduces the neutron flux onthe detectors as well as the radiation footprint of the system.

In the illustrated embodiment, there are two shielding configurations.One configuration shields the neutron generators 18 from the detectors20, and another shields the detectors 20 from as much background as ispossible.

The shielding around the neutron generators 18 includes, for example, 12inches of 5% borated poly, which reduces the neutron flux from theneutron generators 18 by as much as 90%. The neutrons interacting withthe poly create a large amount of 2.2 MeV gamma rays.

In the illustrated embodiment, 4 inches of additional bismuth shieldingis placed between the poly and the detectors 20 to reduce this flux ofgamma rays. The shielding around the sides of the detectors 20 includes,for example, 1 inch of bismuth. This reduces the unwanted gamma raysfrom any interaction the neutrons have with the surrounding material.FIG. 15 is a cut-away perspective view of one of the racks and shows theshielding.

In the illustrated embodiment, the control system 22 has a graphicaluser interface defined by the computer 26. The graphical user interfaceprovides different screens for different levels of users. For example,in the illustrated embodiment, the system has two levels of users,operator and administrator. An operator is, for example, allowed tocheck the status/health of the system and, of course, run the system.The administrator sets up the system originally and has control over allpreferences and settings.

FIG. 3 shows but one example of a main graphical user interface (GUI)screen 28, which the operator would see after the system 10 is firstpowered on. The screen 28 was intentionally simplified, allowing theoperator to quickly determine the status of the system 10. The screen 28indicates, in an area 30, the threat level. The screen 28 indicates, inareas 32 and 34, the progress of the interrogation. The screen 28indicates, in an area 36, status. The screen 28 also indicates, in anarea 39, the voltages and currents for two neutron generators 18. Thestatus area or button 36 displays the health of the system using colors,for example, green indicates that the computer 26 is communicating withall detectors 20 and neutron generators 18, yellow indicates loss ofconnection with at least one detector 20, and red indicates loss ofcommunication with at least a threshold number of detectors 20. Theadministrator of the system sets this threshold. The system has theability to operate even with the loss of detectors 20 but must have atleast a threshold amount. The screen 28 indicates results in an area 38.Area 38 will display one of the following: Idle, Interrogating,Processing, All Clear, or Suspect Cargo. If, at any time, the computer26 loses communication with the neutron generators 18 for more than apredetermined amount of time, such as a few seconds, the neutrongenerators 18 will shut down. Also, as a fail-safe, if the system 10takes longer than a predetermined amount of time for an interrogation,the neutron generators 18, and possibly other parts of the system 10,will shutdown. The screen 28 also includes a reset button 40, whichcauses the screen 28 to refresh; a start button 42, for starting aninterrogation; a stop button 44, for terminating an interrogation; apower button 46, for turning power on to the detectors 20 and neutrongenerators 18 by setting their various parameters, and a close button48, for closing the graphical user interface screen 28 and allowing thecomputer 26 to be used as a conventional computer. The screen 28 alsoincludes a change button 50 that allows the Threat Level to be changed.

FIG. 4 is a screen shot of the graphical user interface screen 28 duringneutron generator start-up (during warm-up).

FIG. 5 is a screen shot of the graphical user interface screen 28 duringdetection using the detectors 20 (FIG. 2).

FIG. 6 is a screen shot of the graphical user interface screen 28 afterdetection using the detectors 20, where no explosives have beendetected. “All Clear” is displayed in area 38.

FIG. 7 is a screen shot of the graphical user interface screen 28 afterdetection using the detectors 20, where explosives have been detected.“Suspect Cargo” is displayed in area 38.

FIGS. 17A and 17B comprise a screen view of an example of anadministrator level screen using operating parameters of detectors thatcan be set.

FIG. 18 is a screen view of an example of an administrator level screenusing operating parameters of generators that can be set.

FIG. 19 is a screen view of an example of an administrator level screenusing operating parameters such as threat level settings and otheritems, as shown, that can be set.

FIG. 8 is a diagrammatical map illustrating the general locations ofdetectors. By grouping multiple detectors together, the system is ableto detect smaller quantities in a shorter amount of time. Also, becauseof the way the detectors are grouped, the detectors are able tointerrogate an entire 20-foot truck. While other groupings are possible,in the illustrated embodiment, groups are defined as follows, eachdetector 20 being more particularly numbered as shown in FIG. 8:

Group 1 includes detectors 201, 202, 203, 204, 205, and 206;

Group 2 includes detectors 203, 204, 205, 206, 207, and 208;

Group 3 includes detectors 205, 206, 207, 208, 209, and 210;

Group 4 includes detectors 207, 208, 209, 210, 211, and 212;

Group 5 includes detectors 209, 210, 211, 212, 213, and 214;

Group 6 includes detectors 211, 212, 213, 214, 215, and 216;

Group 7 includes detectors 217, 218, 219, 220, 221, and 222;

Group 8 includes detectors 219, 220, 221, 222, 223, and 224;

Group 9 includes detectors 221, 222, 223, 224, 225, and 226;

Group 10 includes detectors 223, 224, 225, 226, 227, and 228;

Group 11 includes detectors 225, 226, 227, 228, 229, and 230;

Group 12 includes detectors 227, 228, 229, 230, 231, and 232;

Group 13 includes detectors 201, 203, 205, and 207;

Group 14 includes detectors 203, 205, 207, and 209;

Group 15 includes detectors 205, 207, 209, and 211;

Group 16 includes detectors 207, 209, 211, and 213;

Group 17 includes detectors 209, 211, 213, and 215;

Group 18 includes detectors 202, 214, 216, and 218;

Group 19 includes detectors 204, 206, 208, and 210;

Group 20 includes detectors 206, 208, 210, and 212;

Group 21 includes detectors 208, 210, 212, and 214;

Group 22 includes detectors 210, 212, 214, and 216;

Group 23 includes detectors 217, 219, 221, and 223;

Group 24 includes detectors 219, 221, 223, and 225;

Group 25 includes detectors 221, 223, 225, and 227;

Group 26 includes detectors 223, 225, 227, and 229;

Group 27 includes detectors 225, 227, 229, and 231;

Group 28 includes detectors 218, 220, 222, and 224;

Group 29 includes detectors 220, 222, 224, and 226;

Group 30 includes detectors 222, 224, 226, and 228;

Group 31 includes detectors 224, 226, 228, and 230;

Group 32 includes detectors 226, 228, 230, and 232;

Group 33 includes detectors 201, 202, 203, and 204;

Group 34 includes detectors 203, 204, 205, and 206;

Group 35 includes detectors 205, 206, 207, and 208;

Group 36 includes detectors 207, 208, 209, and 210;

Group 37 includes detectors 209, 210, 211, and 212;

Group 38 includes detectors 211, 212, 213, and 214;

Group 39 includes detectors 213, 214, 215, and 216;

Group 40 includes detectors 217, 218, 219, and 220;

Group 41 includes detectors 219, 220, 221, and 222;

Group 42 includes detectors 221, 222, 223, and 224;

Group 43 includes detectors 223, 224, 225, and 226;

Group 44 includes detectors 225, 226, 227, and 228;

Group 45 includes detectors 227, 228, 229, and 230;

Group 46 includes detectors 229, 230, 231, and 232;

Group 47 includes detectors 201, 203, 205, 217, 219, and 221;

Group 48 includes detectors 203, 205, 207, 219, 221, and 223;

Group 49 includes detectors 205, 207, 209, 221, 223, and 225;

Group 50 includes detectors 207, 209, 211, 223, 225, and 227;

Group 51 includes detectors 209, 211, 213, 225, 227, and 229;

Group 52 includes detectors 211, 213, 215, 227, 229, and 231;

Group 53 includes detectors 202, 204, 206, 218, 220, and 222;

Group 54 includes detectors 204, 206, 208, 220, 222, 224;

Group 55 includes detectors 206, 208, 210, 222, 224, and 226;

Group 56 includes detectors 208, 210, 212, 224, 226, and 228;

Group 57 includes detectors 210, 212, 214, 226, 228, and 230;

Group 58 includes detectors 212, 214, 216, 228, 230, and 232;

Group 59 includes detectors 201, 202, 203, 204, 205, 206, 207, and 208;

Group 60 includes detectors 203, 204, 205, 206, 207, 208, 209, and 210;

Group 61 includes detectors 205, 206, 207, 208, 209, 210, 211, and 212;

Group 62 includes detectors 207, 908, 209, 210, 211, 212, 213, and 214;

Group 63 includes detectors 209, 210, 211, 212, 213, 214, 215, and 216;

Group 64 includes detectors 217, 218, 219, 220, 221, 222, 223, and 224;

Group 65 includes detectors 219, 220, 221, 222, 223, 224, 225, and 226;

Group 66 includes detectors 212, 222, 223, 224, 225, 226, 227, and 228;

Group 67 includes detectors 223, 224, 225, 226, 227, 228, 229, and 230;

Group 68 includes detectors 225, 226, 227, 228, 229, 230, 231, and 232;

Group 69 includes detectors 201, 202, 217, and 218;

Group 70 includes detectors 201, 202, 203, 204, 217, 218, 219, and 220;

Group 71 includes detectors 215, 216, 231, and 232;

Group 72 includes detectors 213, 214, 215, 216, 229, 230, 231, and 232;

Group 73 includes detectors 214, 215, 216, 230, 231, and 232;

Group 74 includes detectors 213, 215, 216, 229, 231, and 232;

Group 75 includes detectors 213, 214, 216, 229, 230, and 232;

Group 76 includes detectors 213, 214, 215, 229, 230, and 231;

Group 77 includes detectors 201, 202, 203, 217, 218, and 219;

Group 78 includes detectors 201, 202, 204, 217, 218, and 220;

Group 79 includes detectors 201, 203, 204, 217, 219, and 220; and

Group 80 includes detectors 202, 203, 204, 218, 219, and 220.

Other groupings, either overlapping or not overlapping, can be used inalternative embodiments. An advantage of this grouping of detectors isthe ability to detect smaller quantities in a shorter amount of time.

FIG. 9 is a flowchart illustrating operation of the control system 22,in accordance with various embodiments.

FIG. 10 is a flowchart illustrating the calibration of FIG. 9 in greaterdetail.

As depicted in FIG. 9, in step 51, operation starts.

In step 52, after the power button 46 is clicked, detectors 20 arepowered on, and neutron generators 18 are initialized. After performingstep 52, the controller proceeds to step 54.

In step 54, an initialization or gain/stabilization run is performed.The detectors are activated by neutrons, and in this step, they areactivated. Spectra tend to shift, and it is desired to stabilize them.In the illustrated embodiment, gain stabilization is a feature of thedigiBASEs®. Gain stabilization means finding a peak and providing thelocation and width of the peak to the digiBASE® so that the digiBASE®can keep that peak from shifting (e.g., along the horizontal axis in anyof FIGS. 11-14). Gain stabilization could also be performed ifdigiBASEs® are not employed. In the illustrated embodiment, after thegain stabilization is complete, the reset button 40 must be pressedbefore proceeding. After performing step 54, the controller proceeds tostep 56.

In step 56, the controller waits for the start button 42 to be pressed.After the start button 42 is pushed, the interrogation starts. Afterperforming step 56, the controller proceeds to step 58.

In step 58, warm-up of the neutron generators 18 is initiated. In theillustrated embodiment, this takes about 85 seconds, other neutrongenerators are warmed up more quickly. During warm-up, voltage is on andcurrent comes up, and pressure in tubes in the neutron generatorsincreases. After performing step 58, the controller proceeds to step 60.

In step 60, after the neutron generators have reached full power and areemitting neutrons, data acquisition is started, using the detectors 20.After performing step 60, the controller proceeds to step 62.

In step 62, after the data acquisition is complete, spectra aredownloaded from the detectors 20 and the neutron generators 18 areturned off. After performing step 62, the controller proceeds to step64.

In step 64, the spectra are calibrated. This step is described ingreater detail below in connection with FIG. 10. After performing step64, the controller proceeds to step 66.

In step 66, spectra are gain shifted to a common calibration. Thisrefers to moving peaks to common channels or energy levels so they canbe added. The term “channel” refers to the horizontal axis in any ofFIGS. 11-14. Different positions along the horizontal axis are differentchannels having different energy levels (energy level increases as youmove to the right of the origin). Because of potential drift, it is notalways known, at first, which channel corresponds to which energy level.Calibration is performed, as shown in FIG. 9, to determine whichchannels correspond to which energy levels.

After performing step 66, the controller proceeds to step 68.

In step 68, all spectra are summed together for each pre-defined group.The summing is performed for each of the groups 1 through 80, describedabove in connection with FIG. 8. After performing step 68, thecontroller proceeds to step 70.

In step 70, nitrogen detection analysis is performed on each summedgroup. This refers to identifying a nitrogen region, and performingstatistical analysis to determine if counts are above a background levelin a region approximately 100 channels wide near 10.8 MeV. There areactually three overlapping peaks, which may not be distinguishable, so arange of channels is analyzed. After performing step 70, the controllerproceeds to step 72.

In step 72, a determination is made as to whether a minimum number ofgroups are above the nitrogen detection threshold. The minimum number ofgroups may be three, for example. If so, the controller proceeds to step74. If not, the controller proceeds to step 76.

In step 74, the controller informs the operator that explosives havebeen detected, by, for example, causing a message such as “SuspectCargo” to be displayed. In alternative embodiments, an audible messageis provided in addition to, or instead of, the display.

In step 76, the controller informs the operator that explosives have notbeen detected, by, for example, causing a message such as “All Clear” tobe displayed. In alternative embodiments, an audible message is providedin addition to, or instead of, the display.

FIG. 10 describes step 64 in greater detail.

In step 100, regions containing peaks are defined, and the peaksthemselves are generally defined using Gaussian curve fitting. FIG. 11is graph showing an example of a typical NaI spectrum. Gaussian curvefitting is known in the art and is described, for example, in thefollowing reference: Debertin, K. and Helmer, R. G., (1988) “Gamma- andX-Ray Spectrometry with Semiconductor Detectors,” Amsterdam, TheNetherlands: Elsevier Science B.V.

After performing step 100, the controller proceeds to step 102.

In step 102, a doublet is located in the annihilation region. A doubletis a pair of overlapping peaks that look like a single peak. As shown inFIG. 12, there is a sodium peak 302 and an annihilation peak 304 whichtogether define a doublet 306. When a positron is slowed down toessentially zero energy, it will interact with an electron, the two willannihilate, and usually two photons of 511 keV will be produced. This511 keV gamma ray, produced by the annihilation of the positron andelectron, forms what is called the annihilation peak. After performingstep 102, the controller proceeds to step 104.

In step 104, a predetermined energy value (e.g., 511 kiloelectron Voltsor keV) is assigned to the centroid channel for one (e.g., therightmost) peak in the doublet 306. An annihilation peak is known tohave an energy value of 511 keV and the rightmost peak in the doublet306 is the annihilation peak 304. The leftmost peak in the doublet 306is a sodium peak 302. After performing step 104, the controller proceedsto step 106.

In step 106, a predicted H2223 peak centroid channel is calculatedusing, for example, a library derived equation. By H2223, what is meantis a Hydrogen peak at approximately 2223.25 keV. More particularly, instep 108, using a library of spectra with known calibrations, predictionequations are developed for a hydrogen 2223.25 keV peak location basedon an annihilation peak location and a 6867.8 keV Na (sodium) peak.After finding the annihilation and sodium peaks (or doublet), thelocation of the hydrogen peak can be predicted using the predictionequations.

After performing step 106, the controller proceeds to step 110.

In step 110, the “best” peak is found in a region surrounding thepredicted H2223 peak location. FIG. 13 is a graph illustrating Gaussianpeak fitting to the hydrogen 2223 peak 308. A predetermined energy value(e.g., 2223.25 keV) is assigned to the centroid channel for the bestpeak. After performing step 110, the controller proceeds to step 112.

In step 112, the controller calculates a linear Na6868 peak centroidchannel by a linear fit to the annihilation and hydrogen peaks. Afterperforming step 112, the controller proceeds to step 114.

In step 114, a nonlinearity adjustment is applied to the linear Na6868peak predicted centroid using the library-derived equation from step108. After performing step 114, the controller proceeds to step 116.

In step 116, the controller finds the best peak in a region surroundingthe predicted Na6868 peak location. FIG. 14 is a graph illustratingGaussian peak fitting to a sodium 6868 peak 310. The controller assigns6867.8 keV to the centroid channel for the best peak.

In step 118, a quadratic equation is fit to the annihilation, hydrogenand sodium peak centroids and energy values to produce the final energycalibration equation. There are many possible ways of fitting aquadratic equation. In the illustrated embodiment, a least squares fitis used. Least squares fits are described, for example, in the followingreference: Debertin, K. and Helmer, R. G., (1988) “Gamma- and X-RaySpectrometry with Semiconductor Detectors,” Amsterdam, The Netherlands:Elsevier Science B.V.

Using a library of existing calibrated spectra to derive predictionequations is believed to be a significant improvement in energycalibration, which results in increased calibration speed and improveddetection capability. The form and actual numerical values for thederived adjustment equations may vary from one application to the next,as well as might the method of deriving the equation from the library ofspectra.

An example, using real numbers will now be provided for each of thesteps. As an example, only, in step 100, the region containing theannihilation peak may be found, using Gaussian curve fitting, to be theregion containing channel 48. In this example, the peak regionboundaries may be found to be, for example, from channel 30 to channel65.

Continuing the example, in step 102, the sodium/annihilation doubletpeak is found within the annihilation region and the doublet is fitusing Gaussian peak fitting. Let us say that, in the example, theannihilation peak centroid channel is found to be at channel 53.9.Continuing the example, in step 104, 511 keV is assigned to channel53.9.

Continuing the example, in step 106, the Predicted Hydrogen PeakCentroid Channel is calculated using the library-derived equation:Predicted Hydrogen Peak Centroid Channel=66.4+2.7*Annihilation PeakCentroid Channel=212.0.

In step 110, the region is then found from the region list containingthe Predicted Hydrogen Peak Centroid Channel. In the example, the regionfrom channel 201 to 236 is found. Gaussian peak fitting is performed tofit the hydrogen peak. In the example, the Hydrogen Peak CentroidChannel is found to be at channel 218.7. 2223.25 keV is assigned to thischannel.

Continuing the example, in step 112, the slope and intercept arecalculated for a linear prediction of the Sodium Peak Centroid Channelas follows (the slash symbol “/” symbolizes division and the asterisksymbol “*” symbolizes multiplication):Slope=(218.7−53.97)/(2223.25−511)=0.096Intercept=53.97−Slope*511=4.79The Linear Sodium Peak Centroid Channel Prediction is then calculated asfollows:Linear Sodium Peak Centroid ChannelPrediction=Intercept+(Slope*6867.8)=665.5

Continuing the example, in step 114, a nonlinear adjustment is appliedto the Linear Sodium Peak Centroid Channel Prediction using alibrary-derived equation to get the Predicted Sodium Peak CentroidChannel, as follows:Predicted Sodium Peak Centroid Channel=Linear Sodium Peak CentroidChannel Prediction+10.25+(−0.11*Linear Sodium Peak Centroid ChannelPrediction)=601.7.

In step 116, in the example, a region (e.g., forty channels wide) isformed on either side of the Predicted Sodium Peak Channel and thesodium peak is fitted using Gaussian peak fitting. A Sodium PeakCentroid Channel is found at channel 606.7. 6867.8 keV is assigned tothis channel.

Continuing the example, in step 118, a quadratic least squarescalculation is fit to the (channel, keV) pairs for the annihilation,hydrogen, and sodium peaks to get the energy calibration equation:Energy in keV=−15.7+9.6*Channel+0.0029*Channel*Channel.

The above was but one example, to better enable one of ordinary skill inthe art to understand the flowcharts. Other examples are, of course,possible depending on actual readings. In alternative embodiments, otherquadratic equation fitting methods can be employed, other than leastsquares.

In some embodiments, the control system is configured to executecomputer program code embodied in a computer readable medium. Theprogram code, when executed in the control system, causes the controlsystem to perform the steps of FIGS. 9 and 10. The computer readablemedium can be any form of RAM, ROM, or EPROM, including CD-ROMs, DVDs,floppy disks, hard drives, memory sticks, tapes, etc. In someembodiments, the program code is embodied in a carrier wave transmittedover a computer network, such as over the Internet. In other words, insome embodiments, computer code which defines the steps of FIGS. 9 and10 can be delivered to a customer or user by transmission over a networksuch as a LAN, WAN, or the Internet.

FIG. 15 is a cut-away perspective view of one of the racks 12 and showsthe detectors 201-216 and neutron generator 18 supported by a frame 240.Insulation 242, e.g., bismuth of about 0.5 to 1 inch thick, surroundseach detector 201-216. Insulation, such as 5% borated poly 244 isprovided around the neutron generator 18. Additional insulation 246 and248, such as 4-inch-thick bismuth, is provided between the neutrongenerator 18 and the detectors 201-206. While other dimensions arepossible, in the illustrated embodiment, the distance from the renter ofone detector to the center of an adjacent detector to the left or rightis 1.5 feet; for example, the distance from the center of detector 202to the center of adjacent detector 204 is 1.5 feet. One of the detectorsis 1.5 feet above the adjacent row; for example, detector 205 is 1.5feet above adjacent detector 206. The horizontal distance from thecenter of detector 208 or 207 to the center of the neutron generator 18is 3 feet. Other spacings are, of course, possible, but this spacing hasbeen designed in particular for interrogation of a mid-sized truck.

FIG. 16 illustrates spacing between components in a rack, in oneparticular embodiment.

The system 10 can be used for military base, border, check point,building and embassy security.

The system 10 is a non-destructive, non-intrusive, and non-contactsystem. In other words, the system 10 can interrogate a vehicle withouta need to open the vehicle and risk the life of the inspector.

The system 10 can detect explosives in a variety of sizes of vehicles,including mid-size delivery trucks, and can detect explosives concealedwithin a vehicle. The system 10 has a measurement and analysis time offive minutes or less. In some embodiments, the system 10 usescommercial, off-the-shelf components as much as possible. Minimaltraining is needed to operate the system 10. Straightforward “go/no-go”reporting is provided. The system 10 can detect explosives such asammonium nitrate and fuel oil (ANFO), pentaerythrite tetranitrate(PETN), composition 4 (C4), trinitrotoluene (TNT), etc. While thepreferred embodiments have been described in connection with detectionof nitrogen, in alternative embodiments, other or additional elementsare detected that may be helpful in deciding whether there areexplosives present.

In compliance with the statute, the invention has been described inlanguage more or less specific as to structural and methodical features.It is to be understood, however, that the invention is not limited tothe specific features shown and described, since the means hereindisclosed comprise preferred forms of putting the invention into effect.The invention is, therefore, claimed in any of its forms ormodifications within the proper scope of the appended claimsappropriately interpreted in accordance with the doctrine ofequivalents.

1. A method of determining a presence of at least one explosive in avehicle, the method comprising: directing energy at a vehicle using aneutron generator; reading spectra from a plurality of NaI detectorsarranged adjacent the vehicle in a plurality of groups comprisingdifferent combination of NaI detectors; calibrating the spectra,comprising: performing Gaussian peak fitting to define peak regions;locating a Na peak and an annihilation peak doublet; assigning apredetermined energy level to one peak in the doublet; and predicting ahydrogen peak location based on a location of at least one peak of thedoublet; gain shifting the spectra to a common calibration; summing thespectra for respective groups of NaI detectors; and performing Nitrogendetection analysis on the summed spectra for each group.
 2. The methodof claim 1, further comprising performing Gaussian peak fitting to finda peak in a region surrounding the predicted hydrogen peak location. 3.The method of claim 2, further comprising predicting a Na peak locationbased on the location of the annihilation peak and the peak found in theregion surrounding the predicted hydrogen peak.
 4. The method of claim2, further comprising predicting a Na peak location using a linear fitto the location of the annihilation peak and the location of thehydrogen peak.
 5. The method of claim 2, further comprising predicting aNa peak location using a linear fit to the location of the annihilationpeak and the location of the hydrogen peak and then applying anonlinearity adjustment.
 6. The method of claim 5, further comprisingproviding a library of spectra with known calibrations and using thelibrary to develop a prediction equation for locating the hydrogen peakand developing the nonlinearity adjustment.
 7. The method of claim 5,further comprising providing a library of spectra with knowncalibrations and using the library to develop the nonlinearityadjustment.
 8. The method of claim 5, further comprising performingGaussian peak fitting to find a peak in a region surrounding thepredicted Na peak location.
 9. The method of claim 8, further comprisingfitting a quadratic equation to the annihilation peak, the hydrogenpeak, and the Na peak to produce an energy calibration equation.
 10. Asystem for determining a presence of at least one explosive in avehicle, the system comprising: a neutron generator located and orientedto direct energy at a vehicle location; a plurality of NaI detectorsadjacent the vehicle location, comprising a plurality of groupscontaining different combinations of the NaI detectors; and a controlsystem configured to: read spectra from the plurality of NaI detectors;calibrate the spectra, comprising: performing Gaussian peak fitting todefine peak regions; locating a Na peak and an annihilation peakdoublet; assigning a predetermined energy level to one peak in thedoublet; and predicting a hydrogen peak location based on the locationof at least one peak of the doublet; gain shift the spectra to a commoncalibration; sum the spectra for respective groups of NaI detectors; andperform nitrogen detection analysis on the summed spectra for eachgroup.
 11. The system of claim 10, wherein the control system is furtherconfigured to perform Gaussian peak fitting to find a peak in a regionsurrounding the predicted hydrogen peak location.
 12. The system ofclaim 11, wherein the control system is further configured to predict aNa peak location based on the location of the annihilation peak and thepeak found in the region surrounding the predicted hydrogen peaklocation.
 13. The system of claim 11, wherein the control system isfurther configured to predict a Na peak location using a linear fit tothe location of the annihilation peak and the location of the hydrogenpeak.
 14. The system of claim 11, wherein the control system is furtherconfigured to predict a Na peak location using a linear fit to thelocation of the annihilation peak and the location of the hydrogen peakand then applying a nonlinearity adjustment.
 15. The system of claim 14,further comprising a library of spectra with known calibrations, andwherein the control system is configured to use the library to develop aprediction equation for locating the hydrogen peak and to develop thenonlinearity adjustment.
 16. The system of claim 14, further comprisinga library of spectra with known calibrations, and wherein the controlsystem is configured to use the library to develop the nonlinearityadjustment.
 17. The system of claim 14, wherein the control system isfurther configured to perform Gaussian peak fitting to find a peak in aregion surrounding the predicted Na peak location.
 18. The system ofclaim 17, wherein the control system is further configured to fit aquadratic equation to the annihilation peak, the hydrogen peak, and theNa peak to produce an energy calibration equation.